Mr
Arturs Zarins
(University of Latvia, Institute of Chemical Physics), Dr
Gunta Kizane
(University of Latvia), Ms
Liga Avotina
(University of Latvia)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
In the frame of EUROfusion consortium programme, Institute of Chemical Physics and Faculty of Chemistry of the University of Latvia are performing investigations on plasma facing, neutron multiplying and self-sufficient tritium generating functional materials for the use of International Thermonuclear Experimental Reactor (ITER) and DEMOnstration power plant.
Be is used as plasma facing...
K.W. Hill
(Princeton Plasma Physics Laboratory)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
X-ray spectroscopy will be used in indirect drive experiments at the National Ignition Facility (NIF) to diagnose plasma conditions and mix in ignition capsules near stagnation times, thus indicating the quality of the implosion, and at various positions in the hohlraum. The electron temperature, Te, and density, ne, will be measured from dielectronic satellites and Stark broadening,...
Dr
Ulrich Fischer
(Karlsruhe Institute of Technology (KIT))
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
Neutronics simulations play an important role for the design and optimisation of the nuclear components of a fusion reactor and the related performance analyses. Accurate data need to be provided to predict the Tritium breeding capability, assess the shielding efficiency, estimate the nuclear power generated in all components, and produce activation and radiation damage data for the irradiated...
Dr
Jay Anderson
(University of Wisconsin)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
The existence of a magnetic-island induced gap in the shear Alfvén continuum was predicted numerically [Biancalani et al. PRL 2010], but only recently have experimental observations of the MIAE been made in stellarator[Sun et al. PPCF 2015] and RFP plasmas [Cook et al. submitted PPCF 2016]. As the role of 3D magnetic fields in tokamaks grows in prominence, associated changes in the Alfvénic...
Dr
Dmitry Moseev
(Max-Planck-Institut für Plasmaphysik)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
W7-X is an optimized stellarator with n=5 toroidal symmetry. It is designed to produce high performance steady-state plasmas. The main heating mechanism is ECRH, which is capable of delivering continuously up to 5 MW with six gyrotrons at 140 GHz and in the next campaign the total power of the ECRH set-up will be increased to 9 MW and 10 gyrotrons. Such a powerful source of microwaves can also...
Dr
Motoki Nakajima
(Japan atomic energy agency)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Water cooled ceramic breeder concept is a primary candidates for ITER and DEMO blankets of Japan. In this blanket, the pressurized water of 15 MPa between 558 K to 598 K is used as the coolant. In such blanket, the structural material is required to be as thin as possible for tritium breeding. However, the pressure tightness is required to withstand 15 MPa of internal pressure. Therefore one...
Dr
Atsushi Ito
(National Institute for Fusion Science)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
To achieve the fuel balance and recycling in ITER and DEMO reactors, it is necessary to understand hydrogen behaviour in plasma facing materials. Because the plasma-wall interaction is determined by particle balance between the flux of plasma particles and the diffusivity in materials, the reproduction of realistic flux and fluence corresponding to experiments is a key issue in simulation. In...
Prof.
Hong Jin Kong
(KAIST)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Laser fusion drivers requires around 40 kJ@10 ps laser for fast ignition. However, it is hard to produce such a high energy, high repetition rate laser because of the thermal problems. The output energy of current high repetition rate laser projects is at most 100 J, even with using the most advanced laser technologies. A coherent beam combining is one of the most promising technique to...
Mr
Hideo Nagatomo
(Osaka University)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Compression and heating of solid spherical target under the strong external magnetic field is studied using fast ignition integrated interconnecting simulation system (FI^3). The simulation results show that (i) a compression of a solid sphere target is stable, and it is possible to achieve a high areal density core plasma. Using GXII scale laser, it will be 60-80 mg/cm^2. (ii) The magnetic...
Prof.
Takayoshi Norimatsu
(Institute of Laser Engineering, Osaka University)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
In this work, we report a conceptual design of a laser fusion experimental reactor (LIFT) and an issue analysis of the design. After the demonstration of ignition and burn by a single shot in fast ignition experiment, construction of an experimental reactor will start. In order to bridge the technological gap between the single-shot experiment and a commercial reactor, an experimental reactor...
Mr
Alexey Razdobarin
(Ioffe Institute)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
According to recent experiments in plasma fusion machines, the contamination of optical elements under deposition-dominated conditions in ITER will result in fast degradation of their optical characteristics. The development of deposition-mitigation techniques is an important part of R&D program of ITER optical diagnostics. The presentation is focused on the approaches to be used for the...
Mr
Stephen M. Manoah
(Institute for Plasma Research)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
SST-2 is under design as an intermediate step before the Indian demo. The design provides a low fusion gain (Q=5) for realizing the reactor technologies and serve as the test bed for qualifying reactor components and D-T fuel cycle. The design is based on RCC-MR code. The Vacuum Vessel (VV) will be constructed out of SS316LN with control over cobalt content (in the range of 0.03%). The design...
Prof.
Xiang Liu
(Southwestern Institute of Physics)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
HL-2M is a new tokamak machine under construction and advanced divertor configuration is one of the major targets. Snowflake and tripod divertor configurations can be performed with up to 3 MA plasma current and 25 MW heating power. The maximal wall load on divertor target plates will reach to 3-7 MW/m2, depending on standard or advanced divertor configurations. Carbon fiber enhanced carbon...
Prof.
JIE YU
(Institute of Nuclear Energy Safety Tech. , CAS)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
China has long been active in pushing forward the fusion energy development to the demonstration of electricity generation. Two experts’ meetings were organized in 2014 by Ministry of Science and Technology (MOST) to seriously discuss the China’s fusion roadmap in particular the design and construction of magnetic confinement fusion reactor beyond ITER.
As one of the most challenging...
Brandon Sorbom
(MIT Plasma Science and Fusion Center)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
The recent commercialization of high temperature superconductors (HTS) has opened up a new parameter space for the design of tokamak fusion pilot plants. The lack of significant critical current degradation at high magnetic fields of HTS allows tokamaks to be designed with much higher on-axis fields. The ARC reactor design study showed that the use of HTS to design a compact, high-field pilot...
Dr
Alexander Spitsyn
(NRC "Kurchatov institute"), Mr
Dmitry Cherkez
(Ilyich), Mr
Nikolay Bobyr
(NRC "Kurchatov institute")
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
In the next step fusion devices, such as DEMO or fusion neutron sources high neutron fluxes and fluences are expected. In this case reduce activated (RA) and heat-resistant structural materials should be used.
In Russia V-(4÷10) Ti-(4÷10) Cr alloys, austenitic and RA ferritic-martensitic steels for fission applications are developed and manufactured in A.A. Bochvar High-technology Research...
Mr
Makoto Oya
(JpUOsaka)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Toughened, Fine-Grained Recrystallized Tungsten (TFGR W) has been developed at Tohoku Univ., Japan [1], in order to improve poor mechanical properties of W such as brittleness at low temperature and embrittlement following neutron irradiation. TFGR W has an average grain size of ~1 µm with a small amount of TiC and TaC dispersoids. These features of the microstructure serve to improve...
Dr
Juergen Rapp
(Oak Ridge National Laboratory)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
Linear plasma generators are cost effective facilities to simulate divertor plasma conditions of present and future fusion reactors. They are used to address important R&D gaps in the science of plasma material interactions and towards viable plasma facing components for fusion reactors.
Next generation plasma generators have to be able to access the plasma conditions expected on the divertor...
Mr
Takuya Nagasaka
(National Institute for Fusion Science)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Reduced-activation ferritic steels and their oxide-dispersion-strengthened (ODS) alloys are promising structural material for fusion blanket. The ODS steels are superior to the non-ODS steels in heat resistance and neutron irradiation resistance, however inferior in mass production. Since high temperature and high neutron dose area is limited at only the first wall section of the blanket,...
Prof.
Yunfeng Liang
(Forschungszentrum Jülich GmbH, Germany)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Plasma–wall interaction (PWI) in the divertor region of Wendelstein 7-X (W7-X) will be of great importance for operational phase OP1.2. While the erosion of the divertor will have an impact on its lifetime and is therefore a critical subject of investigation, fundamental PWI studies in the divertor region are in many ways equally significant. These plasma–wall interactions will be influenced...
Dr
Yasuhisa Oya
(Shizuoka University)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Elucidation of tritium dynamics is one of the key issues for sustainable D-T fusion. Tungsten will be exposed to high fluxes of tritium (T) accompanied with various energetic particles. Therefore, T retention and its trapping states will be dramatically changed by the accumulation of ion and neutron-induced damage and recovery by heating. These facts motivate us to perform extensive hydrogen...
Lorenzo Frassinetti
(KTH, Royal Institute of Technology)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
The plasma braking due to resonant and non-resonant magnetic perturbations (MPs) is experimentally studied in the EXTRAP T2R [1] reversed-field pinch (RFP) and the results compared with theoretical models adapted to the RFP configuration.
The resonant MP produces the tearing mode (TM) braking and, eventually, when the MP amplitude is above the locking threshold, the TM locking. The unlocking...
Dr
Yuji Nobuta
(Hokkaido Univ.)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
In the present study, long-term samples made of stainless steel, which is the same material as the first wall panels in the LHD, were mounted at a lot of places on the plasma-facing surface in the LHD during the 17th experimental campaign (FY2013) and the surface modifications caused by plasma-surface interactions were evaluated. In addition, in order to investigate hydrogen isotopes release...
Prof.
Daniel Den Hartog
(UsUWisMad)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Over the past several decades, numerical simulation has successfully described various dynamical phenomena in fusion research plasmas. Substantial effort is now being applied to enhance the quantitative predictive capability of numerical simulation. Two key tools for this effort are quantitative validation and integrated data analysis (IDA). To perform validation, results of a numerical...
Dr
Sergey Bozhenkov
(Max-Planck Insitute for Plasma Physics)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
In the first Wendelstein 7-X operational campaign a dedicated limiter configuration was used for both helium and hydrogen plasmas. The achievable discharge duration and the heating power depend on the symmetry of power distribution between five limiters. Toroidally asymmetric loads appear due to misalignments and intrinsic error fields. It is found numerically that for misalignments of a few...
Dr
Samuel Lazerson
(Princeton Plasma Physics Laboratory)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
The measurement and correction of error fields in Wendelstein 7-X (W7-X) is critical to long pulse high beta operation, as small error fields may cause overloading of divertor plates. Accordingly, as part of a broad collaborative effort, the detection and correction of error fields on the W7-X experiment has been performed using the U.S. supplied trim coil system [1] in conjunction with the...
Dr
David Brower
(UCLA)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Drift wave turbulence underlies key transport phenomena in toroidal, magnetically confined plasmas. While long-studied for the tokamak and stellarator configurations, the distinguishing features of the reversed field pinch (RFP) allow further development of gyrokinetic models that build on the RFP’s features of high-beta, large magnetic shear (tending to add stability), and relatively weak...
Prof.
George TYNAN
(University of California San Diego)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
We present plasma-implanted D retention and thermo-mechanical properties in ion-beam displacement damaged tungsten targets. Cu ion beams with energies ranging from 0.5-5 MeV induce displacement damage of up to 1 displacement per atom (dpa) in the first micron of the surface in W samples held at a controlled temperature. Damaged samples are then exposed to D plasmas at 300-400 K to decorate...
Dr
Maria Ester Puiatti
(Consorzio RFX)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
RFX-mod is a flexible device capable of operating both as a Reversed Field Pinch and as a Tokamak, both circular and shaped. In both configurations the explored parameter range and the effectiveness in dealing with critical issues for magnetic confinement will be extended by some enhancements aiming at: a) reducing magnetic chaos by improving the performance of MHD control system; b) improving...
Prof.
Yoshitaka Mori
(The Graduate School for the Creation of New Photonics Industries)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Fast heating is a scheme to heat an imploded high density plasma into a hot state before the plasma hydro dynamically expands and dissolves. For a heating process driven by laser induced hot electron currents, the energy of hot electrons beyond MeV having a range of a few g/cm^2, therefore collisional coupling is inefficient until the core density reaches hundreds g/cc. To improve the MeV...
Dr
Stefan Marsen
(Max-Planck-Institut für Plasmaphysik Teilinstitut Greifswald)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
W7-X is a steady state capable optimized stellarator. The main heating system is electron cyclotron resonance heating (ECRH) operating at 140GHz providing up to 9MW microwave power.
A set of diagnostics has been developed to protect the machine from non absorbed ECRH power which can easily damage in vessel components.
The power is launched into the machine by front steerable quasi-optical...
Prof.
Sümer Şahin
(ATILIM University)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
The structural material should have the properties given briefly as below:
• Low neutron absorption cross sections.
• Adequate mechanical properties before and after irradiation.
• Operation at a wide temperature window.
• Working at high temperatures.
• Resistant to atomic displacement and helium generation damage.
• Low activation property under 14 MeV neutrons.
• High thermal...
Dr
Alexey Zhirkin
(NRC “Kurchatov Institute”)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
In this report the requirements to the calculation accuracy of the main parameters of the fusion neutron source and the thermonuclear blankets with the DT fusion power of more than 10 MW are formulated. To conduct the benchmark experiments the technical documentation and calculation models were developed for two blanket micro-models: the molten salt and heavy water solid-state blanket. The...
Dr
Monica Spolaore
(Consorzio RFX, Padova, Italy)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
The RFX-mod experiment is a fusion device designed to operate as a Reversed Field Pinch (RFP), with a major radius R= 2 m and a minor radius a = 0.459 m. Its high versatility recently allowed operating also as an ohmic tokamak allowing comparative studies between the two configurations in the same device. The device is equipped with a state of the art MHD mode feedback control system,...
Dr
Michael Jaworski
(Princeton Plasma Physics Laboratory)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
M.A. Jaworski1,a, A. Brooks1, P. Rindt2, K. Tresemer1, J.-P. Allain3, R.J. Goldston1, T.K. Gray4, R. Kaita1,
N. Lopes-Cardozo2, J. Nichols1, J. Menard1, M. Ono1, D.N. Ruzic3, J. Schwartz1, and the NSTX-U Team
1Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA
2Technological University of Eindhoven, Eindhoven, The Netherlands
3Department of Nuclear, Plasma and Radiological...
Prof.
Mizuki Sakamoto
(Plasma Research Center, JpUTsukuba)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Tungsten is a candidate material for plasma facing components of DEMO as well as divertor plates of ITER, because it has favorable properties such as a very low solubility for hydrogen isotopes. However, surface condition of the plasma facing material is certainly changed by plasma-wall interaction (PWI). Such a surface modification could affect a property of H isotope retention which is a key...
Mr
Kevin Woller
(Massachusetts Institute of Technology)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Helium (He) ion energy modulation is demonstrated, for the first time, to affect the development of the tungsten (W) nano-tendril morphology that results from He irradiation. Dramatically isolated nano-tendril bundles (NTBs) grow from the surface instead of a uniform nano-tendril layer, or so called fuzz, leaving ~90% of the surface without nano-tendril growth at all. The growth parameters for...
Prof.
Sadao Masamune
(Kyoto Institute of Technology)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
We have modified the active MHD control system in RELAX in order to compensate for the sideband effect arising from two poloidal gaps of the vacuum vessel. As a result, the discharge duration has reached iron-core-saturation-limited level with stabilization of the resistive wall mode (RWM). The plasma performance has also been improved; the central electron poloidal beta, the ratio of central...
Dr
Yasunobu Arikawa
(Insituteof Laser Engineering Osaka University)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
In the fast ignition scheme, a fusion fuel is compressed by implosion laser and then heating laser heats the core plasma to ignition temperature. The heating laser interacts with the cone target and fast electrons are accelerated, and the electrons are absorbed by the core plasma so that the core plasma is heated to ignition temperature. Since LFEX (heating laser) energy is limited to 10 kJ at...
Dr
Rajabbay Khaydarov
(IAPh)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
In recent years the ion components of the laser-produced plasmas has been intensively studied as an object to provide high-density and high-energy ion sources, which can be effectively used in the field of inertial confinement fusion. It is well known that processes taking place during the interaction of laser radiation with solid targets strongly depend on the target material leading to...
Prof.
Tao Lan
(University of Science and Technology of China)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Keda Torus eXperiment (KTX) is a medium size reversed field pinch (RFP) machine which has been constructed to study active feedback control of MHD modes, electromagnetic turbulences and plasma wall interaction under different magnetic configurations, such as low safety factor (q) tokamak and reversed field pinch. The variation of magnetic topology in the presence of both external and internal...
Dr
Novimir Pablant
(Princeton Plasma Physics Laboratory)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
The performance of the Wendelstein 7-X (W7-X) stellarator during the first experimental campaign (OP1.1) is explored using measurements from the x-ray imaging crystal spectrometer (XICS) diagnostic. During OP1.1 plasmas have been produced in a limiter configuration, with up to 4 MW of ECH power. The properties of both helium and hydrogen plasmas are investigated.
The XICS system is...
Dr
Toshihiko Shimizu
(Institute of Laser Engineering, Osaka University)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Investigating the fusion plasma is necessary to control the fusion process and to understand the plasma dynamics. Down-scattered (DS) neutrons detection is much suitable for measurement of the areal-density. We have demonstrated that lanthanide-doped 20Al(PO3)3-80LiF (APLF) has excellent characteristics as DS neutron scintillators. In this paper, the properties of lanthanide-doped APLF...
Dr
Andreas Krämer-Flecken
(DeFJ)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
For the first operation phase of the optimized stellarator W7-X, a heterodyn poloidal correlation reflectometry (PCR) diagnostic is installed and in operation. The PCR system consists
of an antennae array with one launching and four receiving antennae. The system is operated in a frequency range 22 GHz to 40 GHz. With the selected O-mode polarization of the system a density range of 0.6 ×...
Dr
Narguess Nemati
(Nuclear Science and Technology Research Institute (NSTR), Plasma Physics and Nuclear Fusion Research School, A.E.O.I., Tehran 14155-1339, Iran)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
10-layered (100 wt.% W- 90 wt. %W/10 wt. %Cu- 80wt. %W/2wt.%0Cu….100wt.%Cu) W/Cu functionally graded material (FGM) with dispersion of Al13Fe4 CMA particles was synthesized by powder metallurgy technique at different temperatures for 1 hour under a load of 650 MPa. The influences of different sintering processes on relative density, hardness, neutron irradiation resistance and microstructure...
Dr
Kunihiro Ogawa
(National Institute for Fusion Science)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
High-temperature and high-density plasmas are achieved by means of real time control, fast diagnostic, and high power heating systems. Those systems are precisely controlled by means of transmission and highly integrated electronic components. However, the radiation damage due to neutron and gamma-ray may lead to serious impact on those systems. Therefore, effects due to irradiation on...
Prof.
Masayoshi Nagata
(University of Hyogo)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Transient Coaxial helicity injection (T-CHI) has been examined in the Helicity Injected Spherical Torus (HIST) device for solenoid-free plasma startup in a ST. Here, we report the formation process of T-CHI start-up plasma including flux-surface closure and fast magnetic reconnection. Experimental observation shows that (i) two or three plasmoids or islands are generated in elongated toroidal...
Prof.
Rajdeep Singh Rawat
(National Institure of Education, Nanyang Technological University, Singapore-637616)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
For the purpose of investigating the damage processes of surface layers during transient heat loads, fuel retention and dust issues of tungsten as candidate plasma facing materials, the International Atomic Energy Agency (IAEA) organized a dedicated Coordinated Research Project (CRP F1.30.13) from 2011-2015. The CRP involved 18 institutions from 15 member states. The activities concentrated on...
Dr
Matteo Agostini
(Consorzio RFX)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Three-dimensional magnetic fields are commonly applied to the plasma edge of fusion devices in order to modify the plasma wall interaction, edge-localized modes (ELM) frequency, divertor loads and transport. However, the action of these magnetic perturbations (MPs) on the edge plasma is still not well understood, and to date there is no obvious relationship between the edge pressure gradient...
Dr
Glen Wurden
(LANL)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
During the first operational phase (OP1.1) of the new W7-X stellarator, five poloidal graphite limiters serve as the main boundary for the plasma. For one of the limiters (Module 3) we have a common sight line for high resolution fast visible and mid-band infrared cameras, as well as filtered photomultipliers. Another limiter (Module 5) is instrumented with tangential view visible and near and...
Dr
Subrata Pradhan
(Institute for Plasma Research, Bhat, Gandhinagar 382428, Gujarat, India)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Runaway dominated low density discharges are modeled for SST-1 using the model as proposed by I El Chamaa Neto et al. [2] for before Plasma Facing component installation and after Plasma Facing component installation. For both the cases modeled results are compared with the measured data. It is found that the runaway generation takes place in the outer region of the Plasma column and the...
Dr
Marius Wirtz
(Forschungszentrum Jülich)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Plasma facing materials (PFMs) for future fusion devices like ITER have to withstand severe environmental conditions such as steady state and transient thermal loads as well as high particle (H, He, n) fluxes. The design and the performance of plasma facing components (PFCs) such as the divertor targets strongly depend on the selection of suitable PFMs, e.g. refractory metals, which meet...
Mr
Philipp Drews
(Forschungszentrum Jülich GmbH,Germany)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Wendelstein 7-X (W7-X), one of the world’s largest stellarators, located at the IPP Greifswald, started operation recently with a limiter configuration. Edge plasma profile measurements, especially those of the electron temperature and density, will play a key role in validating the performance in comparison to the tokamak and hence the viability of a stellarator fusion reactor. The first...
Mr
JASRAJ DHONGDE
(Institute for Plasma Research)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Steady State Superconducting Tokamak (SST-1) is a medium size Tokamak (R/a=1.1/0.2, BT ~1.5T to 3T, IP ~ 102kA) in operation at the Institute for Plasma Research, India. SST-1 has been consistently producing plasma currents in excess of 100kA, with Plasma durations above 250ms and a central magnetic field of 1.5T in recent experimental campaigns of 2016. Investigation of experimental data...
Dr
Andreas Langenberg
(Max-Planck-Institut für Plasmaphysik,17491 Greifswald, Germany)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Starting from the first operation of the Wendelstein 7-X (W7-X) stellarator, the x-ray imaging crystal spectrometer system (XICS) routinely provides line of sight integrated measurements of electron, Te, and ion temperatures, Ti, as well as Ar impurity densities, nAr, based on the spectral emission of an argon tracer impurity. In addition, XICS is capable to measure plasma flow velocities v...
Dr
Heun Tae Lee
(Osaka University)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
To date, the primary method for fuel retention estimates in next step devices has been based on projection of laboratory data with input from gas balance and post-mortem analysis. The use of a large database minimizes risk, but the static nature of the retention data is not amendable to making projections under varied conditions. One recent example would be the failure of predicting how the...
Prof.
Jose Manuel Perlado
(Instituto Fusion Nuclear / UNIVERSIDAD POLITECNICA MADRID)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Multiscale Modeling (MM) demonstrates its important role in the deep understanding of physics mechanisms involved in materials behavior under extreme conditions. Damage of materials by neutrons and ion irradiation in Fusion Systems is progressively better characterized by using a combination of experiments and simulation. It is also possible to give the conditions of Hydrogen (EOS) when...
Dr
Satoshi SATO
(Japan Atomic Energy Agency)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
In order to validate the nuclear data, we performed integral experiments on tungsten, vanadium-alloy (V-4Cr-4Ti) and copper with the DT neutron source at JAEA/FNS over 20 years ago. The calculated results largely underestimated the measured ones sensitive to low energy neutrons. Background neutrons scattered in the concrete wall of the experimental room may cause these underestimations. In...
Prof.
Igor Garkusha
(IPP NSC KIPT)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Understanding of plasma-surface interaction (PSI) effects during the transient events (disruptions, VDEs, ELMs) in tokamak reactor requires dedicated R&D activity in plasma simulators used in close connection with material characterization facilities as well as with theory and modeling activities. For such investigations different simulators of transient loads are now involved (quasistationary...
Dr
Santanu Banerjee
(Institute for Plasma Research)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Study of the plasma dynamics during the termination phase of a tokamak discharge, particularly during a major disruption, is extremely important for gaining an understanding of essential processes that impact operation limits (e.g. the β limit), outward heat and particle flux and plasma control. Behavior of the edge and scrape off layer plasma during such an event is also vital since this...
Mr
JASRAJ DHONGDE
(Institute for Plasma Research)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Steady State Superconducting Tokamak (SST-1) is a medium size operational Tokamak (major radius=1.1m, minor radius=0.2m) at the Institute for Plasma Research (IPR), India [1]. In the recent experimental campaign, SST-1 has successfully achieved plasma current in order of 100kA and plasma duration in excess of ~330ms at a central magnetic field of 1.5T. An attempt has made to observe/study the...
Dr
Sergey Rogozhkin
(SSC RF ITEP of NRC “Kurchatov Institute”)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Oxide dispersion strengthened steels providing exceptional high-temperature creep and irradiation resistance are presently being developed for fusion reactor. Excellent mechanical properties of ODS steels are directly related to the high density of homogeneously distributed, well-formed oxide particles (such as Y2O3, or Y-Ti-O). However, atom probe tomography (APT) study of ODS steels revealed...
Dr
Iole Palermo
(CIEMAT, Fusion Technology Division, Avda. Complutense 40, 28040-Madrid, SPAIN)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
The neutronic radiation coming from the fusion plasma of large machines as the foreseen DEMO could severely affect the stability and the lifetime of the components which constitute the reactor. Nevertheless neutrons are fundamental to allow the reactor to reach the tritium self-sufficiency and to generate and extract enough nuclear power. This means that in the nuclear design of a kind of...
Prof.
Takaaki Fujita
(Nagoya University)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
The fast neutrons produced by DT fusion are able to burn the long-lived biologically hazardous transuranics (TRUs) in the spent fuel discharged from fission light water reactors more efficiently than other sources like fast fission reactors. Although a concept design of such a system employing a conventional tokamak (like ITER) with super-conducting coils as the fusion core was proposed, the...
Prof.
Wandong Liu
(University of Science and Technology of China)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
The Keda Torus eXperiment (KTX) is a new reversed field pinch (RFP) device at the University of Science and Technology of China. KTX is complementary to the existing international Revered Field Pinch (RFP) facilities. KTX includes the vacuum chamber, conducting shell, magnetic field windings, power supply, active control coils, vacuum pump, wall baking and data acquisition system, KTX...
Dr
Arkadi Kreter
(Forschungszentrum Juelich)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
The fuel retention and the lifetime of plasma-facing components are critical plasma-material interaction factors potentially limiting the availability of a magnetic fusion reactor. Linear plasma devices are excellent test beds for investigating specific questions of plasma-material interaction. This contribution summarizes the recent plasma-material interaction studies on the linear plasma...
Mrs
Sylvie Jacquemot
(LULI)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
The EUROfusion ToIFE project, launched in 2014 and gathering 14 European laboratories from 9 different countries, aims at achieving the fundamental understanding required to demonstrate the viability of laser-driven fusion as an alternative road towards sustainable, clean and secure energy source. It hinges on (i) a program of experiments and numerical simulations to understand underlying...
Dr
Jozef ONGENA
(Laboratory for Plasma Physics, Ecole Royale Militaire-Koninklijke Militaire School, 1000 Brussels, Belgium, TEC Partner)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
An important aim of W7-X is to demonstrate fast ion confinement at volume averaged beta values up to 5%, corresponding to plasma densities above 10^20 m^-3. Energetic H or D ions in W7-X with energies 50< E < 100 keV mimic alphas in a reactor. To this end, an ICRH system is prepared for W7-X ,with RF power up to ~1.5 MW at frequencies between 25-38 MHz in pulses up to 10 s. For optimal...
Mr
Dilip C Raval
(Institute for Plasma Research)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
SST-1 Tokamak was successfully commissioned in 2012 and the first plasma was achieved in June 2013 with poloidal limiters having SS 304L as vessel wall material. Due to plasma wall interactions, high-Z impurities released from the vessel wall which in turn cools the plasma by radiation loss. In order to reduce this effect, in 2nd phase of SST-1 refurbishment PFC components were installed in...
Dr
Alessio Morace
(Institute of Laser Engineering, Osaka University)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Fast Ignition (FI) is an alternative approach to Inertial Confinement Fusion (ICF) based on the separation between compression and heating of the equimolar Deuterium-Tritium (DT) fuel capsule. In the FI scheme, the heating is produced by an energetic particle beam, either ions or electrons, generated by an ultra-high intensity laser pulse.
Both in Proton and Fast Electron Fast Ignition high...
Mr
Dilip C Raval
(Institute for Plasma Research)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
The SST-1 start- up studies and development of appropriate model has been initiated using electromagnetic field computation for active current carrying conductor and SST-1 vacuum vessel eddy characteristics. This electromagnetic model has been employed to predict individual electromagnetic field for active electromagnet such as vertical field coil (VF), poloidal field coil (PF), radial control...
Dr
Katsuhiro Ishii
(The Graduate School for the Creation of New Photonics Industries)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
The progress of the target injection system is reported, where deuterated polystyrene (CD) beads are injected and engaged by implosion and heating laser beams at the repetition rate of 1 Hz. Since the high repetition rate experiments require to accurately position the injected pellets, for two years we have continuously tested and made the positions of the injected pellets better. Measuring...
Dr
Atsushi Kasugai
(National Institutes for Quantum and Radiological Science and Technology (QST/Rokkasho))
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
In the beam commissioning of the injector of linear IFMIF prototype accelerator (LIPAc) at the International Fusion Energy Research Center in Rokkasho, Japan the initial target performances was accomplished for Radio Frequency Quadrupole (RFQ) accelerator, of which assembling and commissioning will be started in 2016.
At present, 100 keV/120 mA/20% duty cycle deuterium and 50 keV/74 mA/10%...
Prof.
Takashi Kikuchi
(Nagaoka University of Technology)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Recent activities on heavy ion inertial fusion in Japan are reviewed in this paper. Particle accelerator development, beam dynamics research, interaction between heavy ions and target material, ion source development, and illumination scheme of heavy ion beams, for heavy ion inertial fusion, are reported.
Inertial confinement fusion scheme driven by intense heavy ion beams, so-called Heavy...
Prof.
NING DING
(Institute of Applied Physics and Computational Mathematics)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Fast Z-pinch has produced the most powerful X-ray radiation source in laboratory and also shows the possibility to drive inertial confinement fusion (ICF). The recent advances in the Z-pinch theoretical and numerical researches at the IAPCM are presented. We use a detailed circuit model to study the energy coupling between the generator and the Z-pinch process. With the full circuit model (FCL...
Dr
Eiichi Wakai
(Japan Atomic Energy Agency)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Small specimen test technology or technique (SSTT) towards design of fusion DEMO reactors was investigated and evaluated in the related studies of the International Fusion Materials Irradiation Facility / Engineering Validation and Engineering Design Activities (IFMIF/ EVEDA) project under Broader Approach (BA) Agreement between EURATOM and Japanese Government. The main results were described...
Dr
Andrey Litnovsky
(Forschungszentrum Juelich, Germany)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Due to its low sputtering yield, excellent thermal conductivity and low tritium uptake tungsten is currently deemed as most promising plasma facing material (PFM) for future power plant DEMO. However, in case of an accident the coolant supply may be damaged. The air can get into contact with PFMs during the air ingress. According to modeling, the temperature of PFMs can rise up to 1200oC due...
Mr
Jie Liu
(Institute of Applied Physics and Computational Mathematics)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
We propose a feasible scheme to acquire high ion temperature and high thermal nuclear fusion neutron yield with laser ablated spherical convergent plasmas fusion (SCPF). In our scheme, we use intense lasers (1014-1015W/cm2) pulse of nanosecond duration to irradiate thermonuclear fuel (Carbonized Deuterium, CD)containing layer(~10microns) lined inside a spherical hohlraum, the fuel layer is...
Prof.
Qunying Huang
(CnINEST)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
A program for fusion reactor structural material, i.e. the China Low Activation Martensitic (CLAM) program, aims to satisfy the material requirements for test blanket module (TBM) for ITER, China fusion engineering test reactor (CFETR) and fusion demonstration reactor (C-DEMO) in China. It has been undertaking by INEST (Institute of Nuclear Energy Safety Technology), CAS (Chinese Academy of...
Prof.
Akihiko Kimura
(Kyoto University)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Materials development is essential for realization of fusion DEMO reactor and beyond. High performance materials R&D has been conducted for the last several decades, and there have been made some remarkable technology innovations of fusion blanket structural material including first wall material. Among the several candidate blanket structural materials, oxide dispersion strengthened (ODS)...
Prof.
Irina Tazhibayeva
(KzIAE)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
TThe research goal is irradiation of tungsten samples in hydrogen and post irradiation studies of the samples for microstructure change after irradiation and comparison with non-irradiated samples. The tungsten samples of DF-grade, double forged pure, were manufactured in Julich, Germany.
Irradiation of tungsten samples was carried out at the WWR-K reactor of Institute of Nuclear Physics,...
Dr
Riju Chavaramplackil Issac
(PG & Research Department of Physics, Mar Athanasius College, Mahatma Gndhi University, Kothamangalam, Kerala, India)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
In this paper we present our experimental study for the development and investigation of suitable materials for protecting the IFE chamber wall from scattered laser light, energetic ions, electrons, neutrons, X-rays, etc. bombarding the chamber wall causing damage or activation in the wall material. We choose the carbon nanotubes for the following reasons. Carbon nanotubes with its structural...
788.
Temperature Sensitivity Analysis of Nuclear Cross Section using FENDL for Fusion-Fission System
Dr
Carlos Velasquez
(Universidade Federal de Minas Gerais)
20/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
Fusion energy has been presented as a clean alternative way of energy source. Furthermore, the neutronics features from fusion reactors make favorable the fuel regeneration and actinide transmutation due to the high-energy neutron flux. This work proposes a fusion-fission system (FFS) based on a Tokamak at operating temperature for transmutation of MA using reprocessed fuel by UREX+ technique...
Dr
Frederik Arbeiter
(Karlsruhe Institute of Technology)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Validation activities for key systems of the Lithium Facility and the Test Facility of the International Fusion Materials Irradiation Facility IFMIF were performed during the Engineering Validation and Engineering Design Activities phase 2007 - 2015 by Japanese and EU Research Units. A fully functional lithium loop with a 1:3 scaled target were constructed and run in Oarai, Japan. The lithium...
Dr
Andreas Dinklage
(Max-Planck-Institut für Plasmaphysik)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Continuous fueling is a prerequisite for steady-state stellarator and heliotron fusion reactor operation. For 3D magnetic field configurations, outward directed thermodiffusion gives rise to density depletion in the hot plasma core which needs to be compensated by appropriate fuelling schemes. Pellet injection may generate particle sources relevant to the development of discharge scenarios...
Dr
Andrei Simakov
(Los Alamos National Laboratory)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Low-mode implosion asymmetry and hydrodynamic instabilities of the capsule are considered the main obstacles for achieving ignition in indirect drive inertial confinement fusion (ICF). Superior ablation properties of beryllium (Be) ablators as compared with plastic and diamond ablators may help overcome these obstacles. In particular, higher Be ablation pressure permits use of either thicker...
Dr
Olaf Grulke
(MPI for Plasma Physics)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
The understanding of cross-field transport of particles and energy represents one of the most important challenges on the verge towards magnetic confinement fusion and is indispensable to extrapolate to next-generation devices. The Wendelstein 7-X (W7-X) stellarator, designed to operate quasi steady-state (pulse lengths up to 30min), has been optimized with respect to a reduction of...
Dr
Rita Lorenzini
(Consorzio RFX)
20/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
This work describes the development and the first applications of a new tool to study transport phenomena in fusion devices when magnetic islands are present.
Whether as large islands or narrow chains, magnetic islands change drastically the topology of the transport problem and the consequent strong modification of transport has effects that depend on the configuration under examination....
Dr
Jan Willem Coenen
(Forschungszentrum Juelich GmbH)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
The development of advanced materials is essential for sophisticated energy systems like a future fusion reactor. For a fusion power plant multiple issues with respect to materials and components need to be evaluated. Brittle behavior is the limiting factors when operating any W based plasma facing components (PFCs) in a tokamak. This is particularly crucial when considering material...
Prof.
Yoneyoshi Kitagawa
(The Graduate School for the Creation of New Photonics Industries)
20/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
The recent key physics of the laser fusion is how to make hot sparks for the alpha burning in the dense core. The fast ignition is expected to form a hot spark even with a non-uniform illumination configuration, such as with a counter-illumination one. By using both a high-repetition rate 10 J laser and a single-shot kJ laser, we have proposed and demonstrated a new concept for the...
Dr
Hiroo Kondo
(Japan Atomic Energy Agency)
20/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
We report the validation results of liquid lithium target stability for an intense fusion neutron source, currently being planned as the International Fusion Materials Irradiation Facility (IFMIF), the advanced fusion neutron source (A-FNS), or the DEMO oriented neutron source (DONES). Thickness variation of the Li target must be suppressed to be within 1 mm inside a deuteron beam footprint to...
